دانلود مقالات ISI درباره Sgtr + ترجمه فارسی

چارچوب تشخیص خطا با گره های سنسور چند منبع در نیروگاه های هسته ای بر اساس یک شبکه بیزی

Framework for fault diagnosis with multi-source sensor nodes in nuclear power plants based on a Bayesian network

Keywords: ACP; AC power; APPRCS; Average primary pressure in a reactor coolant system; BN; Bayesian network; CPTs; Conditional probability tables; DST; Dempster-Shafer theory; FCL (1); Flow of coolant in loop 1; FCL (2); Flow of coolant in loop 2; FCL (3); Flow o

دانلود رایگان متن کامل مقاله ISI 12 صفحه سال انتشار : 2018 سفارش ترجمه

اثرات سرعت گاز و اندازه شکست در عمق نفوذ بخار با استفاده از جت گاز به آزمایشات شباهت آب

Effects of gas velocity and break size on steam penetration depth using gas jet into water similarity experiments

Keywords: Lead-based reactor; SGTR; Penetration depth; Visualization; Dimensional analysis;

دانلود رایگان متن کامل مقاله ISI 7 صفحه سال انتشار : 2017 سفارش ترجمه

تجزیه و تحلیل هیدرولیکی حرارتی سه بعدی هسته راکتور بر اساس روش رسانه متخلخل

Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media method

Keywords: Reactor pressure vessel; Thermal-hydraulic analysis; Porous media; SGTR; Computational fluid dynamics;

دانلود رایگان متن کامل مقاله ISI 13 صفحه سال انتشار : 2017 سفارش ترجمه

Discussion on emergency response capability configuration for inherent safe HTR

Keywords: DBAs; Design Basis Accidents; ICPD; Ingestion and Commodities planning distance; EPZ; Emergency Planning Zone; FCPZ; Food control planning zone; IEPZ; Ingestion Emergency Planning Zone; ECCS; Emergency Core Cooling System; OILs; Operational Intervention L

دانلود رایگان متن کامل مقاله ISI 8 صفحه سال انتشار : 2018 سفارش ترجمه

Investigation on response of HPR1000 under different mitigation strategies after SGTR accident

Keywords: HPR1000; SGTR; SG overfill; Radioactive release;

دانلود رایگان متن کامل مقاله ISI 9 صفحه سال انتشار : 2018 سفارش ترجمه

Investigation of single bubble rising velocity in LBE by transparent liquids similarity experiments

Keywords: Lead-based reactor; SGTR; Bubble migration; Bubble rising velocity;

دانلود رایگان متن کامل مقاله ISI 10 صفحه سال انتشار : 2018 سفارش ترجمه

Numerical investigation of in-vessel core coolability of PWR through an effective safety injection flow model using MELCOR simulation

Keywords: SAMG; In-vessel coolability; Safety injection flow map; Oxidation heat; Core exit temperature; MELCOR; ADV; Atmospheric Dump Valve; AFW; Auxiliary Feed Water; BWR; Boiling Water Reactor; CDV; Condenser Dump Valve; CET; Core Exit Temperature; CV; Control V

دانلود رایگان متن کامل مقاله ISI 11 صفحه سال انتشار : 2018 سفارش ترجمه

Assessment of primary and secondary bleed and feed procedures during a Station Blackout in a German Konvoi PWR using ASTECV2.0

Keywords: ACCUs; Accumulators; AM; Accident Management; CET; Core Exit Temperature; CVCS; Chemical and Control Volume System; DGs; Diesel Generators; ECCS; Emergency Core Cooling System; EOPs; Emergency Operating Procedures; FOM; Figure of Merit; FW; Feedwater; HPI

دانلود رایگان متن کامل مقاله ISI 17 صفحه سال انتشار : 2018 سفارش ترجمه

Evaluation of JRC source term methodology using MAAP5 as a fast-running crisis tool for a BWR4 Mark I reactor

Keywords: A; activity; AC; alternating current; ASTEC; accident source term evaluation code; BWR; boiling water reactor is a type of light water nuclear reactor; DC; direct current; DOSE; MAAP5 module for the dose calculation; ECCS; emergency core cooling system; E

دانلود رایگان متن کامل مقاله ISI 9 صفحه سال انتشار : 2016 سفارش ترجمه

The core design of ALFRED, a demonstrator for the European lead-cooled reactors

Keywords: CZP; cold zero-power; DBA; design basis accidents; DEC; design extension conditions; DPA; deterministic and phenomenological analyses; ELFR; European lead-cooled fast reactor; FA; fuel assembly; HFP; hot full-power; HZP; hot zero-power; ISAM; integrated s

دانلود رایگان متن کامل مقاله ISI 15 صفحه سال انتشار : 2014 سفارش ترجمه

Thermal-hydraulic analysis of SMART steam generator tube rupture using TASS/SMR-S code

Keywords: SMART; TASS/SMR-S; SGTR; Integral leak; Thermal-hydraulic; CSS; containment spray system; FMHA; flow mixing header assembly; FTC; fuel temperature coefficient; FWIV; feedwater isolation valve; IAPWS; international association for the properties of water s

دانلود رایگان متن کامل مقاله ISI 10 صفحه سال انتشار : 2013 سفارش ترجمه

Common Risk Target for severe accidents of nuclear power plants based on IAEA INES scale

Keywords: ABWR; Advanced Boiling Water Reactor (GE-Hitachi); ACRP; American Committee for Radiation Protection; (US)AEC; United States Atomic Energy Commission (today US NRC); AIDS; Acquired Immune Deficiency Syndrome; ALARA; As low as reasonably achievable; ALARP;

دانلود رایگان متن کامل مقاله ISI 20 صفحه سال انتشار : 2013 سفارش ترجمه

Investigating the appropriateness of a decision chart to characterize the level of task descriptions in nuclear power plants

Keywords: Task description level; Operation experience; Subjective difficulty; Procedure; Nuclear power plant; CST; Condensate Storage Tank; DEG; Designated means; DETAIL; Detailed level description; EOP; Emergency Operating Procedure; gpm; Gallon per minute; INH;

دانلود رایگان متن کامل مقاله ISI 11 صفحه سال انتشار : 2013 سفارش ترجمه

Attenuation of radioactive releases from NPP under accident conditions: An experimental research on risk-dominant scenarios

Keywords: Severe accident; SGTR; Fission product; Aerosol retention; Decontamination factor;

دانلود رایگان متن کامل مقاله ISI 11 صفحه سال انتشار : 2013 سفارش ترجمه

Analysis of the operator action and the single failure criteria in a SGTR sequence using best estimate assumptions with TRACE 5.0

Keywords: SGTR; TRACE; RADTRAD; FSAR; Offsite dose; MTO

دانلود رایگان متن کامل مقاله ISI 17 صفحه سال انتشار : 2013 سفارش ترجمه

Association rules analysis of human factor events based on statistics method in digital nuclear power plant

Keywords: Human factor events; A weight association rules; Dynamic function; SGTR

دانلود رایگان متن کامل مقاله ISI 5 صفحه سال انتشار : 2011 سفارش ترجمه

Investigation of primary to secondary leakage at low power during “Hydro-test” for VVER440/V230 at Kozloduy NPP

Keywords: ANS; American national standard; BAS; Bulgarian Academy of Sciences; BRU-K; Steam Dumping Device to the Condenser (Bulgarian abbreviation); CSF; Critical Safety Function; EFWS; Emergency Feed Water System; FSIV; fast safety isolation valve; FWST; feed wat

دانلود رایگان متن کامل مقاله ISI 15 صفحه سال انتشار : 2011 سفارش ترجمه